SciTech Connect

Title: Thermal-hydraulic aspects of flow inversion in a research reactor

Thermal-hydraulic aspects of flow inversion in a research reactor PARET, a neutronics and thermal-hydraulics computer code, has been modified to account for natural convection in a reactor core. The code was then used to analyze the flow inversion that occurs in a reactor with heat removal by forced convection in the downward direction after a pump failure. Typical results are shown for a number of parameters. Research reactors normally operating much above ten MW are predicted to experience nucleate boiling in the event of a flow inversion. Comparison with experimental results from the Belgian BR2 reactor indicated general agreement although nucleate boiling that was analytically predicted was not noted in the BR2 data.
Authors: ;
Publication Date:
OSTI Identifier:6819218
Report Number(s):CONF-861185-7
ON: DE87004751; TRN: 87-008016
DOE Contract Number:W-31109-ENG-38
Resource Type:Conference
Resource Relation:Conference: Reduced Enrichment for Research and Test Reactors (RERTR) program international meeting, Gatlinburg, TN, USA, 3 Nov 1986
Research Org:Argonne National Lab., IL (USA)
Country of Publication:United States
Language:English
Subject: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; FLUID FLOW; P CODES; REACTOR COOLING SYSTEMS; RESEARCH AND TEST REACTORS; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID MECHANICS; MECHANICS; REACTOR COMPONENTS; REACTORS; SIMULATION 220600* -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors; 420400 -- Engineering-- Heat Transfer & Fluid Flow